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Boron +, Iodine +, Hydrogen +  and Sulfur +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 2 +, 10 CFR 50.62 +, 10 CFR 50.92 +, 10 CFR 51.22 +, 10 CFR 2.714 +, 10 CFR 2.714#a1i +, 10 CFR 50.91#a +, 10 CFR 51.12#b +, 10 CFR 51.22#b +  and 10 CFR 50.92#c +

05000146  +, 05000219  +, 05000250  +, 05000251  +, 05000255  +, 05000261  +, 05000266  +, 05000271  +, 05000272  +, 05000277  +, 05000280  +, 05000281  +, 05000282  +, 05000285  +, 05000301  +, 05000302  +, 05000306  +, 05000311  +, 05000313  +, 05000315  +, 05000316  +, 05000317  +, 05000318  +, 05000324  +, 05000325  +, 05000327  +, 05000328  +, 05000331  +, 05000333  +, 05000336  +...

Turbine Trip +  and Reactor Trip +

59 FR 53834 +, 59 FR 39588 +, 59 FR 52005 +, 58 FR 50963 +, 59 FR 47165 +, 59 FR 9254 +, 59 FR 48917 +, 59 FR 41802 +, 59 FR 27052 +, 59 FR 10005 +, 59 FR 14889 +, 59 FR 47168 +, 59 FR 34665 +, 58 FR 59753 +, 59 FR 34668 +, 59 FR 44432 +, 59 FR 37083 +, 58 FR 12269 +, 59 FR 32237 +, 59 FR 47182 +, 59 FR 27068 +, 59 FR 14897 +, 59 FR 29637 +  and 58 FR 67864 +

Adensam E +  and Office of Nuclear Reactor Regulation +

NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +, NRC Generic Letter 88-15, Electric Power Systems - Inadequate Control Over Design Process +, NRC Generic Letter 90-09, Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions +, NRC Generic Letter 93-08, Relocation of Technical Specification Tables of Instrument Response Time Limits +  and NRC Generic Letter 93-05, Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation +

ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +, ML071040017 +  and ML071040017 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

General Electric +  and Westinghouse +

NUREG-1431 +, NUREG-1433 +, NUREG-1430 +  and NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +

ML071040017 +  and ML071040017 +

NEDO-31400 +  and NEDO-analysis +

SR-4.8.1.1 +, SR-4.5.2.d.3 +, SR-4.6.2.1.c +, SR-4.6.1.2.a +  and SR-4.6.1.2.d +

Manual Scram +  and Automatic Scram +

Millstone +, Calvert Cliffs +, Davis Besse +, Peach Bottom +, Salem +, Nine Mile Point +, Palisades +, Palo Verde +, Point Beach +, Oyster Creek +, Grand Gulf +, Sequoyah +, Byron +, Arkansas Nuclear +, Braidwood +, Susquehanna +, Prairie Island +, Brunswick +, Surry +, Limerick +, Turkey Point +, Vermont Yankee +, Crystal River +, Callaway +, Duane Arnold +, Robinson +, San Onofre +, Cook +, Fort Calhoun +, FitzPatrick +...

Millstone +, Calvert Cliffs +, Salem +, Palisades +, Palo Verde +, Oyster Creek +, Sequoyah +, Byron +, Braidwood +, Susquehanna +, Surry +, Turkey Point +, San Onofre +, NPF-51 +, DPR-51 +, NPF-66 +, NPF-30 +, DPR-49 +, DPR-24 +  and DPR-27 +

Ohio +, Tennessee +, Pennsylvania +, Connecticut +, Arizona +, Illinois +, Minnesota +, Maryland +, North Carolina +, Washington +, California +, Virginia +, New Jersey +, South Carolina +, New York +, Michigan +, Wisconsin +, Florida +, Missouri +, Indiana +, Mississippi +, Nebraska +, Arkansas +, Vermont +  and Iowa +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Control Room Emergency Ventilation +, Standby Liquid Control +, Residual Heat Removal Service Water +, Spray Pond +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Rod Worth Minimizer +, Control rod blade +, Main Condenser +, Control Rod +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +

TS-3.7.3 +, TS-3.5.2 +, TS-3.6 +, TS-3.7 +, TS-3.0.4 +, TS-3.8.1.1 +, TS-1.1 +, TS-2.4 +, TS-3.2 +, TS-3.9.4 +, TS-4.8.1.1 +, TS-3.3.7.1 +, TS-6.8.1 +, TS-3.3 +, TS-6.8.4.a +, TS-1.9 +, TS-4.6.E +, TS-6.8.4 +, TS-4.6 +, TS-3.9.10.2 +  and TS-6.9.3.3 +

Safe Shutdown +, Unanalyzed Condition +, Shutdown Margin +, Reactor Vessel Water Level +, Offsite Dose Calculation Manual +, Enforcement Discretion +, Scram Discharge Volume +, Process Control Program +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Exemption Request +, Fuel cladding +, Failure to Scram +  and Overspeed +